OOIR: Observatory of International Research

Papers

(The median citation count of Science and Technology of Nuclear Installations is 1. The table below lists those papers that are above that threshold based on CrossRef citation counts [max. 250 papers]. The publications cover those that have been published in the past four years, i.e., from 2020-11-01 to 2024-11-01.)

Article	Citations
The Advancement of Neutron Shielding Materials for the Storage of Spent Nuclear Fuel	23
Multiobjective Core Reloading Pattern Optimization of PARR-1 Using Modified Genetic Algorithm Coupled with Monte Carlo Methods	18
Multiple Assessments on the Gamma-Ray Protection Properties of Niobium-Doped Borotellurite Glasses: A Wide Range Investigation Using Monte Carlo Simulations	11
Research on Simulation and State Prediction of Nuclear Power System Based on LSTM Neural Network	11
A New Precursor Integral Method for Solving Space-Dependent Kinetic Equations in Neutronic and Thermal-Hydraulic Coupling System	10
Effect of Thickness and Compaction Degree of Overburden Soil on Radon Reduction for Uranium Tailings Reservoir	9
An Efficient Scheme for Coupling OpenMC and FLUENT with Adaptive Load Balancing	8
The Investigation on Heat Transfer Characteristics of Steam Condensation in Presence of Noncondensable Gas under Natural Convection	8
The Research of Fault Diagnosis of Nuclear Power Plant Based on ELM-AdaBoost.SAMME	7
Coincidence Summing Factor Calculation for Volumetric γ-ray Sources Using Geant4 Simulation	7
Pressure Distribution on the Inner Wall of the Volute Casing of a Centrifugal Pump	6
Experimental Study on Unsteady Radon Exhalation from the Overburden Layer of the Uranium Mill Tailings Pond under Rainfall	6
A Correlation-Based Feature Selection Algorithm for Operating Data of Nuclear Power Plants	6
Cold Atmospheric Plasma Inhibits the Proliferation of CAL-62 Cells through the ROS-Mediated PI3K/Akt/mTOR Signaling Pathway	5
Integrity Evaluation of a Reactor Pressure Vessel Based on a Sequential Abaqus-FRANC3D Simulation Method	5
RELAP5 Foresight Thermal-Hydraulic Analysis of Hypothesis Passive Safety Injection System under LOCA for an Existing NPP in China	5
Design, Experiment, and Commissioning of the Spent Fuel Conveying and Loading System of HTR-PM	4
Reliability Assessment for a Safety-Related Digital Reactor Protection System Using Event-Tree/Fault-Tree (ET/FT) Method	4
Neutronic Performance of the VVER-1000 Reactor Using Thorium Fuel with ENDF Library	4
COMSOL Simulation for Design of Induction Heating System in VULCAN Facility	4
Remaining Useful Life Prediction of Nuclear Power Machinery Based on an Exponential Degradation Model	4
Interim Storage of the Dalat Nuclear Research Reactor: Radiation Safety Analysis	4
Development and Testing of TRACE/PARCS ECI Capability for Modelling CANDU Reactors with Reactor Regulating System Response	4
Migration Simulation of Radioactive Soil Particles in the Atmospheric Environment Using CFD-DEM Coupled with Empirical Formulas	4
Studies on Optimal Strategy to Adopt Nuclear Power Plants into Saudi Arabian Energy System Using MESSAGE Tool	4

Thermomechanical Analysis of a Reactor Pressure Vessel under Pressurized Thermal Shock Caused by Inadvertent Actuation of the Safety Injection System	4
An Economic Cost Assessment on HALEU Fuels for Small Modular Reactors	4
Effectiveness of Serpentine Concrete as Shielding Material for Neutron Source Facility Using Monte Carlo Code	3
Debris Bed Self-Leveling Mechanism and Characteristics for Core Disruptive Accident of Sodium-Cooled Fast Reactor: Review of Experimental and Modeling Investigations	3
Design, Experiment, and Commissioning of the Passive Residual Heat Removal System of China’s Generation III Nuclear Power HPR1000	3
Simulation of Ionizing/Displacement Synergistic Effects on NPN Bipolar Transistors Irradiated by Mixed Neutrons and Gamma Rays	3
Control Rod Modeling and Worth Calculation for a Typical 1100 MWe Nuclear Power Plant Using WIMS/D4 and CITATION	3
Nuclear Power Sustainability Path for China from the Perspective of Operations	3
Technical Options and Cost Estimates for Spent Nuclear Fuel Management at the Barakah Nuclear Power Plants	3
Public Health Effects of Radioactive Airborne Effluents from Nuclear and Coal-Fired Power Plant	3
Radiation Resistance of a Structural Material Based on Modified Titanium Hydride	3
Influence of Weak Compressibility on the Hydrodynamic Performance Evaluation of Pump Turbines in the Pump Mode	3
A Novel and High-Precision Method for Calculating the γ-Ray Build-Up Factor for Multilayer Shields	3
Numerical Investigation on Turbulent Flow and Heat Transfer of Helium-Xenon Gas Mixture in a Circular Tube	3
Manufacturing and Testing of an In Situ Stretching Sample Environment Equipment for Neutron Scattering Experiments	3
Xe Ion Irradiation-Induced Microstructural Evolution and Hardening Effect of Nickel-Base Superalloy	3
Investigation of Early Corrosion Behavior of Canister Candidate Materials in Oxic Groundwater by the EQCM Method	3
An Information Granulated Based SVM Approach for Anomaly Detection of Main Transformers in Nuclear Power Plants	3
Benchmark Analysis on Loss-of-Flow-without-Scram Test of FFTF Using Refined SAC-3D Models	3
Mechanical Properties Evaluation and Crack Propagation Behavior in Dissimilar Metal Welded Joints of 304 L Austenitic Stainless Steel and SA508 Low-Alloy Steel	3
Power Level Control of Nuclear Power Plant Based on Asymptotical State Observer under Neutron Sensor Fault	3
Metallic Fuel Fabrication Process Development in Remote Fuel Fabrication Mock-Up at KAERI	2
Electrochemical Deposition of U and RE Elements Using the Stirred Liquid Cadmium Cathode in LiCl-KCl Molten Salts	2
Inerting Strategy for a Demonstration-Scale Hot Cell Facility Based on Experiences from Pilot-Scale Argon Cell Facility Operation and CFD Analysis	2
Experimental and Numerical Studies of AP1000 Shield Building considering Fluid-Structure Interaction	2
Cracking Driving Force at the Tip of SCC under Heterogeneous Material Mechanics Model of Safe-End Dissimilar Metal-Welded Joints in PWR	2
Experimental Research for CHF Sensitivity of Heat Flux Distribution under IVR Conditions	2
Study on Probabilistic Safety Goals for Multimodule High-Temperature Gas-Cooled Reactor Based on Chinese Societal Risks	2
Steady-State Thermal-Hydraulic Analysis of the LEU-Fueled Dalat Nuclear Research Reactor	2
A Digital Controller for Reactivity Monitoring and Power Control	2
Uranium Decontamination from Waste Soils by Chlorination with ZrCl4 in LiCl-KCl Eutectic Salt	2
High-Temperature Corrosion Behavior of Incoloy 800H Alloy in the Impure Helium Environment	2
Single-Vehicle Transportation Security System of Radioactive Materials Based on Group Relationship to Prevent Loss and Theft	2
Analysis and Estimation of Core Damage Frequency of Flow Blockage and Loss of Coolant Accident: A Case Study of a 10 MW Water-Water Research Reactor-PSA Level 1	2
Methodology for Establishing Segmentation Strategy for Large Metal Components from Nuclear Power Plants with Consideration of Packaging into Containers	2
Study on the Sensitivity and Uncertainty of Nuclear Data to the Sodium-Cooled Linear Breed-and-Burn Fast Reactor Using SCALE6.2 Code	2
Dynamic Simulation of a Warship Control Valve Based on a Mechanical-Electric-Fluid Cosimulation Model	2
Innovative Design of Compact Heavy-Load Independent Transfer Device for Nuclear Engineering System	2
Feasibility Study on the Initial Kartini Reactor Core Using Plate Type Fuel Elements	2
Source Term Estimation under the SBLOCA-Induced Severe Accident Condition in the SMART	2
Effect of Chloride Ions on Electrochemical Behavior of Canister Materials	2
Overview on Radiation Damage Effects and Protection Techniques in Microelectronic Devices	1
Study of the Design and Assembly of a High Harmonic Fast Wave Antenna for an LAPD	1
Accident Sequence Precursor Analysis of an Incident in a Japanese Nuclear Power Plant Based on Dynamic Probabilistic Risk Assessment	1
Studying Disturbance Wave Velocity and Wall Shear Stress of Vertical Upward Annular Flow in Narrow Rectangular Channel	1
Time-Series Forecasting of a Typical PWR Undergoing Large Break LOCA	1
Numerical Study of the Air Ingress Accident of the HTR-PM and Possible Mitigation Measures	1
A Reduced Order Model Based on ANN-POD Algorithm for Steady-State Neutronics and Thermal-Hydraulics Coupling Problem	1
Study on the Dispersion of Radionuclides under Different Hydrological Conditions of Spent Fuel Shipping in Daya Bay	1
Development of Fuel Product Barrier Monitoring System Based on State Functions in State-Oriented Emergency Operating Procedure	1

Numerical Study of Unsteady Pressure Fluctuation at Impeller Outlet of a Centrifugal Pump	1
Numerical Study of Natural Circulation Flow in Reactor Coolant System during a Severe Accident	1
Research and Implementation of SVDU Simulator Based on Emulation Technology	1
Development of an Integrated Human Error Simulation Model in Nuclear Power Plant Decommissioning Activities	1
Modelling and Validation of CANDU Shim Operation Using Coupled TRACE/PARCS with Regulating System Response	1
Effect of Inhomogeneous Mechanical Properties on the Stress-Strain Field at the Crack Tip and Crack Growth Direction in Dissimilar Metal Welded Joints	1
Cross Flow Analysis over the Jet Pumps of a BWR-5 Reactor	1
ELSMOR European Project: Experimental Results on an Innovative Decay Heat Removal System Based on a Plate-Type Heat Exchanger	1
Shielding Design and Dose Evaluation for HTR-PM Fuel Transport Pipelines by QAD-CGA Program	1
Dissolution Behavior of Simulated Spent Nuclear Fuel in LiCl-KCl-UCl3 Molten Salt	1
Neutron Transport Simulations of RBMK Fuel Assembly Using Multigroup and Continuous Energy Data Libraries within the SCALE Code	1
Preliminary Study on Risk Identification and Assessment Framework for Fusion Radioactive Waste Management	1
Prediction of the Loss of Feed Water Fault Signatures Using Machine Learning Techniques	1
Rapid Determination of Gross Alpha/Beta Activity in Water Based on Reverse Osmosis Membrane Enrichment Pretreatment	1
Experimental Study of Onset of Nucleate Boiling in Vertical Rectangular Channels with Different Flow Path Heights	1
Detection of Illegal Movement in Radioactive Material Transportation Security Systems	1
Machine Learning-Based Approach for Hydrogen Economic Evaluation of Small Modular Reactors	1
Verification of CENDL-3.2 Nuclear Data on VENUS-3 Shielding Benchmark by ARES Transport Code	1
Research on Channel Modeling and Communication Coverage of Wireless Sensor Networks in Barrier Area of Nuclear Power Plants	1
Interaction of Mechanical Heterogeneity and Residual Stress on Mechanical Field at Crack Tips in DMWJs	1
Failure Fraction Calculation of the TRISO-Coated Particle Using X-Ray Computed Tomography	1
Source Reconstruction of Atmospheric Releases by Bayesian Inference and the Backward Atmospheric Dispersion Model: An Application to ETEX-I Data	1
An Improved Steady-State and Transient Analysis of the RSG-GAS Reactor Core under RIA Conditions Using MTR-DYN and EUREKA-2/RR Codes	1
Uranium Recovery from Phosphates for Self-Sufficient Nuclear Power in the Eastern Mediterranean	1
Calculation and Analysis of the Source Term of the Reactor Core Based on Multivariate Analysis of Variance	1
Prediction of Automatic Scram during Abnormal Conditions of Nuclear Power Plants Based on Long Short-Term Memory (LSTM) and Dropout	1
Acceptable Level of Acceptance and the Affecting Factors: What Is the Acceptable Public Acceptance of Building a Nuclear Power Plant	1
Integrated Security System (ISS) Design and Evaluation for Commercial Nuclear Power Plant	1
Study of Clogging Phenomenon for a Conical Hopper: The Influence of Particle Bed Height and Hopper Angle	1
Characterization of Waste Generated from Nuclide Management Process in Waste Burden Minimization Technology for Spent Nuclear Fuel	1
Study on the Applicability of Neutron Radiation Damage Method Used for High-Temperature Superconducting Tape Based on Geant4 and SRIM	1
Study on Airborne Radionuclide Dispersion in Floating Nuclear Power Plant under the Loss-of-Coolant Accident	1
Assessing the Impact of Common Cause Failures on Site Risk within Level 1 Multi-Unit PSA	1
Study on Release and Migration of Radionuclides under the Small Break Loss of Coolant Accident in a Marine Reactor	1
Development and Experimental Validation for Quantifying the Moisture Carryover in a Moisture Separator Using an Air/Water Test Facility	1